TEM characterization of irradiated microstructure of Fe-9%Cr ODS and ferritic-martensitic alloys

JOURNAL OF NUCLEAR MATERIALS

卷:502

Article

Swenson, M. J.^1,2  Wharry, J. P.³ 

[1] Univ Idaho, 875 Perimeter Dr, Moscow, ID 83844 USA

[2] Boise State Univ, 1910 Univ Dr, Boise, ID 83725 USA

[3] Purdue Univ, 400 Cent Dr, W Lafayette, IN 47907 USA

关键词: Dislocation loops;    Voids;    Ion irradiation;    Neutron irradiation;    Oxide dispersion strengthened;    Ferritic-martensitic;   

DOI  :  10.1016/j.jnucmat.2018.01.062

来源: Elsevier

【 摘 要 】

The objective of this study is to evaluate the effects of irradiation dose and dose rate on defect cluster (i.e. dislocation loops and voids) evolution in a model Fe-9%Cr oxide dispersion strengthened steel and commercial ferritic-martensitic steels HCM12A and HT9. Complimentary irradiations using Fe2+ ions, protons, or neutrons to doses ranging from 1 to 100 displacements per atom (dpa) at 500 degrees C are conducted on each alloy. The irradiated microstructures are characterized using transmission electron microscopy (TEM). Dislocation loops exhibit limited growth after 1 dpa upon Fe2+ and proton irradiation, while any voids observed are small and sparse. The average size and number density of loops are statistically invariant between Fe2+, proton, and neutron irradiated specimens at otherwise fixed irradiation conditions of similar to 3 dpa, 500 C. Therefore, we conclude that higher dose rate charged particle irradiations can reproduce the neutron irradiated loop microstructure with temperature shift governed by the invariance theory; this temperature shift is similar to 0 degrees C for the high sink strength alloys studied herein. (C) 2018 Elsevier B.V. All rights reserved.

【 授权许可】

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